Nuclear Materials and Energy英文简介

The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy.Nuclear Materials and Energy is supported scientifically by the Max-Planck-Institut für Plasmaphysik, Garching.The emphasis of the journal is on materials employed in reactors where they are exposed to extreme environments in terms of radiation, temperature and corrosive conditions. The main topics are:Fusion reactor materials, including plasma-facing components, such as divertors, limiters blankets, and the first wall.Material erosion and transport in the boundary of fusion plasmas and its effect on the incident plasma conditions.Interaction of plasmas, ion beams, electron beams and intense heat fluxes with materials with emphasis on lifetime, tritium retention and permeation, and structural stability.Fission reactor materials, including fuels, cladding, moderator, control rods, core structures, pressure vessels, but excluding fuel cycle from mining to nuclear waste.Fusion and fission reactor materials enduring radiation doses at very high temperature far beyond the capability of materials now available for components.Materials behaviour in the interaction with reactor coolants during normal operation and in accidental conditions.Materials behaviour addressing the release of fuel, activated dust and reaction products during accidental conditions, and the physical and chemical interactions of reactor core and containment materials.Neutron and charged particle radiation effects in materials, including defects, gas retention and permeation, transmutations, microstructural changes, phase changes and macroscopic properties.

Nuclear Materials and Energy中文简介

开放获取的《核材料与能源》杂志致力于日益增长的核材料在核能生产中的应用研究领域。核材料和能源由加兴的马普学会提供科学支持。该杂志的重点是在反应堆中使用的材料，他们暴露在极端环境的辐射，温度和腐蚀条件。主要议题包括:聚变反应堆材料，包括等离子体表面组件，如转向器、限流罩和第一壁。聚变等离子体边界的物质侵蚀和输运及其对入射等离子体条件的影响。等离子体、离子束、电子束和热流与材料的相互作用，强调材料的寿命、氚的保留和渗透以及结构的稳定性。裂变反应堆材料，包括燃料、包层、慢化剂、控制棒、核心结构、压力容器，但不包括从采矿到核废料的燃料循环。聚变和裂变反应堆材料在非常高的温度下承受辐射剂量，远远超出了目前可用于组件的材料的能力。在正常运行和意外情况下与反应堆冷却剂相互作用时的材料行为。处理在意外情况下燃料、活性粉尘和反应产物的释放，以及堆芯和密封材料的物理和化学相互作用的材料行为。中子和带电粒子在材料中的辐射效应，包括缺陷、气体保持和渗透、透射、微观结构变化、相变和宏观性质。

Nuclear Materials and Energy中科院分区

Nuclear Materials and EnergyJCR分区